동향

Nuclear Technology Vol.126, No.2, MAY 1999


Technical paper Experimental and analytical Investigation of the Operation Mode of the Emergency Condenser of the SWR1000 Assessment of the Severe Accident Mitigation Features of the European Pressurized Water Reactor by Cooperative Research and Development FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package Evaluating Code Uncertainty-I: Using the CSAU Method for Uncertainty Analysis of a Two-Loop PWR SBLOCA Evaluating Code Uncertainty-II: An Optimal Statistical Estimator Method to Evaluate the Uncertainties of Calculated Time Tends Studies on the Shielding Properties of Polyboron and Illmenite-Magnetite Concrete Using a Reactor Neutron Beam Self-Excited Plutonium X-Ray Emission in Plutonium-Bearing Materials The Volatility of lodine from Irradiated lodide Solutions in the Presence or Absence of Painted Surface: Modeling Work on the IODE Code at IPSN
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